ENDF/B-VIr4 adopted. ENDF/B-VIr6 updated the neutron width of the 8.16eV resonance by a factor 10. Parameters are based on Mughabghab 1973. Correction in Mughabghab 1984.
Gives a significant reduction to the resonance integral.
Diagnostic: Adopt ENDF/B-VIr6 (or correct the neutron width).
This is an old evaluation. Watch for a new ENDF evaluation (ORELA)soon. Quick review by J Rowlands:-
"I have looked in Mughabghab's latest evaluation (Feb 2003) and I see that he gives a resonance integral of 665 +/- 22. (I assume this corresponds to the
lower value of the resonance width, although I am not certain about this). This compares with 761.4 in JEF-2.2 and 720.2 in the 1993 version of B-VI.
It looks as though there might already have been a problem of a difference between JEF-2.2 and B-VI even before this correction was made to the 8.16 eV
resonance, perhaps as a consequence of the use of random assignment of spins. However, I think that it is necessary to get hold of the resonance analysis
(Masyanov+, Russia AE 73 673, Feb 1993 and Huffman ORELA PR/C 54 2051 Oct 1996), and the resonance integral measurements (de Corte+, Hungary? JRN 169
125 Mar 1993)." JEF2.2 used MLBW - policy decision. JEFF3 is back to SLBW - as evaluator intended.

Submitted

76-Os-nat

JEFF30N7600_1.ASC

A. HogenbirkJEF/DOC-911

April 2002

Problems in gamma production (decay scheme incorrect). The decay scheme was corrected by adding data for MF12,MT51 and MF14,MT51. These data were taken from NSR, the Nuclear Structure File (see file Os-nat.txt)

Submitted

82-Pb-207

JEFF30N8234_3.ASC

A. HogenbirkJEF/DOC-911

April 2002

Problems in gamma production (decay scheme incorrect). The decay scheme was corrected by adding data for MF12,MT53 and MF14,MT53. These data were taken from ENDF/B-VI.8 (see file Pb-207.txt).

Submitted

92-U-238

JEFF30N9237_4.ASC

C. Jouanne

7 Feb. 2003

The incident energy range of the delayed neutron spectrum (MF=5, MT=455) is different from the energy range of the corresponding multiplicity (MF=1, MT=455). Indeed, the delayed neutron multiplicity is given for incident neutron energy ranging from 1.E-5 eV to 20 MeV while the spectra of the 8 families are given for two incident energies 1.E+6 eV and 1.4E+7 eV (see file U-238.txt).

Submitted

94-Pu-239

JEFF30N9437_3.ASC

H. Wienke

April 2002

Unresolved resonance range representation: line number 2151 1303 L=1, AJ=1.0 --> AMUN should be 2.0 in stead of 1.0

The secondary energy distribution for (n,2n) has neutron spectra for
each neutron. (MF=5, MT=16). The second neutron has the probability and
corresponding emitted neutron distribution tabulated from an incident
neutron energy of 7.30157 MeV whereas the threshold is at 7.3017 MeV. This
is not seen by FIZCON but causes our monte Carlo processing to fail.

Submitted

82-Pb-207

JEFF30N8234_3.ASC

C. Dean (from R. MacFarlane)

3 Dec. 2004

Information from the NJOY user group stated that there are
no gamma multiplicities (MF12/MT53). This is required according to
procedure 12, section 12.2 of the ENDF-6 formats manual. This could
be solved by insert MF12/MT53 and set the conditional probability (GP)
to a small number (see file Pb207.txt)

Submitted

*: Z-sym-A and state if not ground**: File name as in the official CD-ROM